NSTX-U Research Highlights and Plans

1. NSTX-U Supported by NSTX-U Research Highlights and Plans Jonathan Menard, PPPL For the NSTX Research Team Coll of Wm & Mary Columbia U CompX General Atomics FIU INL Johns Hopkins U LANL LLNL Lodestar MIT Lehigh U Nova Photonics ORNL PPPL Princeton U Purdue U SNL Think Tank, Inc. UC Davis UC Irvine UCLA UCSD U Colorado U Illinois U Maryland U Rochester U Tennessee U Tulsa U Washington U Wisconsin X Science LLC Culham Sci Ctr York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U U Tokyo JAEA Inst for Nucl Res, Kiev Ioffe Inst TRINITI Chonbuk Natl U NFRI KAIST POSTECH Seoul Natl U ASIPP CIEMAT FOM Inst DIFFER ENEA, Frascati CEA, Cadarache IPP, Jülich IPP, Garching ASCR, Czech Rep IAEA FEC Meeting October 2012

2. NSTX research targets predictive physics understanding needed for fusion energy development facilities • Enable key ST applications • Move toward steady-state ST FNSF, pilot plant • Close key gaps to DEMO • Extend understanding to tokamak / ITER • Leverage ST to develop predictive capability Fusion Nuclear Science Facility (FNSF) ST Pilot Plant Present Research • Develop key physics understanding to be tested in unexplored, hotter ST plasmas • Study high beta plasma transport and stability at reduced collisionality, extended pulse • Prototype methods to mitigate very high heat/particle flux • Move toward fully non-inductive operation ITER NSTX-U New center-stack 2nd Neutral Beam

3. Disruption detection & warning analysis of NSTX being developed for disruption avoidance in NSTX-U, potential application to ITER Disruptivity Warning Algorithms • Disruption warning algorithm shows high probability of success • Based on combinations of threshold based tests; no machine learning • All discharges since 2005 with 1/3 ms sampling time • Recorded equilibrium and kinetic parameters, disruption statistics Statistics for a single threshold test Statistics of full warning algorithm DBpn=1 >~15 G used to detect disruption • Physics results • Minimal disruptivity at relatively high bN ~ 6; bN / bNno-wall(n=1) ~ 1.3-1.5 • Consistent with specific disruption control experiments • Strong disruptivity increase for q* < 2.5 • Strong disruptivity increases for lowest rotation • Results & Physics implications • ~98% disruptions flagged with at least 10ms warning, ~6% false positives • Most false positives are due to “near disruptive” events • Early MHD slows wf • recoverable Z motion Gerhardt EX/9-3

4. Exploring electromagnetic massive particle delivery system with potential advantages over conventional methods for disruption mitigation in ITER • Well suited for long stand-by mode operation: • Large particle inventory • All particles delivered at nearly the same time • Particles tailored to contain multiple elements in different fractions and sizes • Single system for varying initial plasma parameters • Tailored particles fully ionized only in higher current discharges • Particle penetration not impeded by B-fields • Toroidal nature and conical disperser ensures that: • - The capsule does not enter the tokamak intact • The capsule will fragment symmetrically and deliver a uniform distribution of particles (or via. tapered final section) • Coaxial Rail Gun is a fully electromagnetic system with no moving parts, so should have high reliability from long stand-by mode to operate on demand: • Conventional gas guns will inject gas before capsule Injector Capsule • Detailed design of a proto-type system now underway R. Raman et al, U. Washington 4

5. Measurements of global stability vs. collisionality support kinetic RWM stability theory, provide guidance for NSTX-U, ITER-AT Exp: Resonant Field Amplification (RFA) vs n Theory: RWM growth rate contours (gtw) “off resonance” Marginal Stability unstable NSTX NSTX-U “on resonance” Collisionality Plasma Rotation MISK code • Two competing effects at lower n • Collisional dissipation reduced • Stabilizing resonant kinetic effects enhanced (contrasts early theory) • Expectations at lower n • More stabilization near ωφ resonances; almost no effect off-resonance • Mode stability directly measured in experiment using MHD spectroscopy • Decreases with n at lower RFA (“on resonance”) • Independent of n at higher RFA (“off resonance”) Bplasma RFA = Bapplied Berkery EX/P8-07 J. Berkery et al., PRL 106, 075004 (2011)

6. Find plasma characteristics change nearly continuously with increasing Li evaporation; also testing ELM stability theory • ELMing plasmas reach kink/peeling limit • Improved bootstrap current calculation in pedestal (XGC0) yields improved agreement with marginal stability Energy Confinement Time (ms) Pre-discharge lithium evaporation (mg) • Global parameters generally improve • ELM frequency declines - to zero • ELMs stabilize • Edge transport declines • As lithium evaporation increases, transport barrier widens, pedestal-top χereduced Diallo EX/P4-04 Maingi EX/11-2 Canik EX/11-2 Chang TH/P4-12

7. PPPL Lithium Granule Injector tested on EAST Dennis Mansfield (PPPL, retired) Lane Roquemore (PPPL) JianshengHu and D. Mansfield 6 inch Dropper Independent Control: Granule Size (change between shots) Injection Speed (ramp during shots) Pacing Frequency (ramp during shots) 5.5 inch Li Granules 8 inch V = 0 - 100 m/s Freq = 0 - 100 Hz 10 mm

8. Triggered ~25Hz ELMs with 0.7mm Li granules at ~ 45 m/s  potentially very useful for triggering ELMs in Li-ELM free H-modes in NSTX-U, also ITER?

9. Pedestal width scaling similar to other experiments, but width is larger; turbulence correlation lengths consistent with theory Pedestal width scaling Turbulence correlation lengths Theory: non-linear XGC1, Expt: BES Radial ~ 3 cm Poloidal ~ 11 cm R = 1.38m • Measured correlation lengths are consistent with theory • Radial (reflectometry) ~ 2 – 4 cm • Poloidal (BES) ~ 10 – 14 cm • spatial structure exhibits ion-scale microturbulence (kqriped ~ 0.1 - 0.2) • Pedestal width scaling bqa applies to multiple machines • In NSTX, observed ped. width is larger • 1.7 x MAST, 2.4 x DIII-D • Data indicates stronger for NSTX: bq0.94 vs. bq0.5 Diallo EX/P4-04 A. Diallo, C.S. Chang, S. Ku (PPPL), D. Smith (UW), S. Kubota (UCLA) 9 9

10. Nonlinear microtearing simulations for NSTX consistent with measured electron heat transport dependence on collisionality Theory Experiment • Predicted ce and scaling ~ ne1.1 consistent with experiment (WtE ~ BttE ~ n*e-0.8) • Transport dominated by magnetic “flutter” • dBr/B ~ 0.1% - possibly detectable by planned UCLA polarimetry system dBr (Gauss) experiment BttE(T-s) cesim ~ ne1.1 120968 W. Guttenfelder, et al., PRL 106, 155004 (2011) n*e(at r/a = 0.5) • Increase in tE as n*e decreases • Trend continues when lithium is used Kaye EX/7-1 Guttenfelder TH/6-1 • NSTX-U computed to extend studies down to < 1/4 of present n*

11. Significant fraction of the NSTX HHFW power may be lost in the SOL in front of antenna and flow to the divertor region • View from Top • Divertor HHFW Antenna • Divertor HHFW Antenna SPIRAL results show field lines (green) spiraling from SOL in front of HHFW antenna to divertor Visible camera image shows edge RF power flow follows magnetic field from antenna to divertor • R. J. Perkins, et al., PRL (2012) Perkins EX/P5-40 • Field line mapping predicts RF power deposited in SOL, not at antenna face • 3D AORSA will assess surface wave excitation in NSTX-U • NSTX-U experiments and modeling to emphasize HHFW heating of high NBI power, long-pulse H-modes  assess effect of varying outer gap

12. 100% non-inductive NSTX-U operating points projected for range of toroidal fields, densities, and confinement levels Projected Non-Inductive Current Levels for k~2.85, A~1.75, fGW=0.7 BT=1.0 T, IP=1 MA, Pinj=12.6 MW • From GTS (ITG) and GTC-Neo (neoclassical): • ci,ITG/ci,Neo~ 10-2 • Assumption of neoclassical ion thermal transport should be valid Contours of Non-Inductive Fraction Contours of qmin

13. NSTX-U team continuing to strongly support ITER throughparticipation in ITPA joint experiments and activities NSTX typically actively participates in ~25 Joint Experiments/Activities • Advanced Scenarios and Control (4) • IOS-1.2 Study seeding effects on ITER baseline discharges • IOS-4.1 Access conditions for advanced inductive scenario with ITER-relevant conditions • IOS-4.3 Collisionality scaling of confinement in advanced inductive plasmas • IOS-5.2 Maintaining ICRH coupling in expected ITER regime • Boundary Physics (10) • PEP-6 Pedestal structure and ELM stability in DN • PEP-19 Edge transport under the influence of resonant magnetic perturbations • PEP-23 Quantification of the requirements of ELM suppression by magnetic perturbations from internal off mid-plane coils • PEP-25 Inter-machine comparison of ELM control by magnetic field perturbations from mid-plane RMP coils • PEP-26 Critical edge parameters for achieving L-H transitions • PEP-27 Pedestal profile evolution following L-H/H-L transition • PEP-28 Physics of H-mode access with different X-point height • PEP-31 Pedestal structure and edge relaxation mechanisms in I-mode • PEP-32 Access to and exit from H-mode with ELM mitigation at low input power above PLH • DSOL-24 Disruption heat loads • Macroscopic Stability (5) • MDC-2 Joint experiments on resistive wall mode physics • MDC-4 Neoclassical tearing mode physics – aspect ratio comparison • MDC-14 Rotation effects on neoclassical tearing modes • MDC-15 Disruption database development • MDC-17 Physics-based disruption avoidance • Transport and Turbulence (7) • TC-9 Scaling of intrinsic plasma rotation with no external momentum input • TC-10 Experimental identification of ITG, TEM and ETG turbulence and comparison with codes • TC-12 H-mode transport at low aspect ratio • TC-14 RF rotation drive • TC-15 Dependence of momentum and particle pinch on collisionality • TC-17 r* scaling of the intrinsic torque • TC-19 Characteristics of I-mode plasmas • Wave-Particle Interactions (4) • EP-2 Fast ion losses and redistribution from localized AEs • EP-3 Fast ion transport by small scale turbulence • EP-4 Effect of dynamical friction (drag) at resonance on non-linear AE evolution • EP-6 Fast ion losses and associated heat loads from edge perturbations (ELMS and RMPs)

14. Rapid progress being made on NSTX Upgrade ProjectFirst plasma anticipated mid-2014 NEW Center Stack Old center stack Beam box craned over NSTX • 2nd NBI box moved into place • 1 month ahead of schedule TF OD = 20cm TF OD = 40cm Box + cryo-panels next to NSTX • Center-stack upgrade TF conductors being fabricated

15. Formulating FY2014-18 5 year plan to access new ST regimes with Upgrade + additional staged & prioritized upgrades NSTX Upgrade research goals in support of FNSF and ITER • Low collisionality plasma regimes • 100% non-inductive operation • Long-pulse, high power divertor • Advanced high-b scenarios 1 MA Plasma Upgrade Outage 1.5  2 MA Plasma New Center-Stack HHFW Upgrade ECH/EBW 1MW 2 MW LLD Moly-tile 2nd NBI 0.5 MA CHI New Center-stack 1 MA CHI / Plasma Gun CHI Control Coils 0.5 MA Plasma Gun Long–pulse Divertor “Snowflake” Secondary PP option NCC Upgrade Primary PP option 2nd NBI NOTE: Upgrade operation would be delayed ~1 year to mid-2015 w/o incremental, other follow-on upgrades are further delayed Existing coils Lithium Non-axisymmetric Control Coils (NCC)

16. Backup Collaboration Highlights

17. H-mode power threshold and confinement / ELM study at KSTAR • Dependence of L-H power threshold (Pthr) on density revealed roll-over at ne ~ 2e19 m-3, while there is no such a dependence in the present multi-machine scaling laws. • Four types of ELMy H-mode were identified even with low NBI power (PNBI = 1.5MW); (1) large type-I ELMs with H98=0.8-0.9, (2) intermediate (possibly type-III) ELMs with H98=0.6-0.8, (3) mixed (type-I + small) ELMs with H98=0.9-1.0, and (4) small ELMs with H98=0.8-0.9 Measured L-H power threshold in low density regime1 Profile measurement for type-I ELMy H-mode shows that the recovery of Ti pedestal after the ELM crash only occurs at the last stage of the inter-ELM period, i.e. > 80 % of the ELM cycle. Vt and Te pedestal continue to build up during the whole ELM cycle. 1J-W. Ahn, ORNL submitted to NF (2012) Vt and Ti profile evolution during the ELM cycle1

18. MAST-NSTX collaboration testing sensitivity of BES to microtearing turbulence through synthetic diagnostics Density fluctuation (rms) • Using nonlinear NSTX microtearing simulations from GYRO with synthetic diagnostic for MAST BES • Difficult to detect MT with expected signal-to-noise ratio (uncorrelated noise dominates) • If S/N can be increased (e.g. significant time averaging) MT features may be measurable, such as: detectable correlated fluctuation levels (dn/n~0.1%) large poloidal correlation lengths (Lp~15-20 cm) Future plans: • Pursue non-linear simulations for MAST discharges with available BES data • Propose experiments for FY13 at next MAST research forum (Dec 2012) to focus on relationship between collisionality scaling and microtearing turbulence Poloidal correlation from synthetic diagnostic (without noise) W. Guttenfelder, et al. PPPL

19. Kinetic neoclassical effects in DIII-D H-mode pedestal using XGC0   To help answer important questions on edge rotation, main-ion physics and SOL flows. Preliminary results using XGC0 simulation of edge main-ion velocity driven by X-loss Deuterium edge velocity measured by Mach Probe J.A. Boedo et al., PoP 18 032510 (2011) Initial profile End of simulation D. Battaglia et al., (PPPL)

20. 3-D Field Effects on Divertor Detachment Explored in ASDEX-U Temporal evolution of divertor heat flux profile during the divertor gas puff and 3-D field application • Deuterium gas puffing induced power detachment at outer divertor but particle detachment was only produced by additional nitrogen puffing • 3-D fields (n=2) application reduced the inner divertor power density but there was no change at the outer divertor. • Applied 3-D fields reduced particle detachment at the outer divertor, which is consistent with the NSTX result. 3-D fields brought the outer divertor heat zone back in, closer to the strike point (sign of power re-attachment, similar to the observation in NSTX) although the particle detachment was becoming stronger. This data suggests that there is a possibility of a de-coupling of the power and particle detachments. J-W. Ahn et al. ORNL

21. Material erosion studies at C-Mod(high-Z wall and low-Z coatings) • LLNL postdoc on-site at Alcator C-Mod tokamak • Novel LLNL intensified camera diagnostic for molybdenum and boron erosion studies • Camera installed and calibrated, contributing to physics operations • Improving techniques for accounting for continuum and Plank emissions • Analyzing moly and boron limiter erosion and core moly penetration factors including RF, inner-wall startup, and boronization effects • Collaboration with ADAS consortium on improved Mo I and Mo II atomic physics calculations for gross and net erosion measurements Pre-boronization 1120613003 0.2s Post-boronization 1120614002 0.2s Vlad Soukhanovskii et al., LLNL LLNL moly camera viewing geometry Mo I emission pre- and post-boronization in C-Mod

22. NSTX Dust Detector Demonstrated on Tore Supra C. Skinner et al, PPPL

23. Lithium transport near divertor target being studied with Magnum-PSI linear test stand Lithiated Target • Transport of eroded lithium needed for plasma modeling and PFC development • Heat flux reduction via lithium radiation in the SOL – how does it get there? • Control of lithium inventory critical to reactors to avoid tritium codeposition and build-up • Magnum-PSI reproduces divertor plasmas on target • Lithiated TZM example shown • Emission profiles in known background plasma provide basis for testing transport models Plasma Source Li-I emission during exposure Li-I emission profile Shorter decay length Found in higher density center λcenter ~ 5mm λedge ~ 13mm M. Jaworski et al, PPPL